Lizhen Tan
机构: Oak Ridge National Laboratory
每年引用次数
引用次数
引用: 6,414
H-指数: 41
I10-指数 : 82
出版物: 188
Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709
Haixuan XU , Lizhan Tan , Kumar Sridharan , Li He
Office of Scientific and Technical Information (OSTI)
2018
Microstructural Effects on the Corrosion Behavior of Alloys and Ceramics
Lizhen Tan , Todd Allen
2008
Plasma-Based Surface Modification and Corrosion in High Temperature Environments
Kumar Sridharan , Todd Allen , Lizhen Tan , WISCONSIN UNIV-MADISON
2009
Microstructural Evolution of Type 304 Variants and 316 Stainless Steels under Neutron Irradiation
Maxim N Gussev , Kevin G Field , Jeremy T Busby , Lizhen Tan
3
2013
Development of Advanced 9Cr Ferritic-Martensitic Steels and Austenitic Stainless Steels for Sodium-Cooled Fast Reactor
Yukinori Yamamoto , Lizhen Tan , Sam Sham
4
2013
PHASE STABILITY OF HIGHLY IRRADIATED AUSTENITIC ALLOYS DURING DEFORMATION
Thak Sang Byun , Maxim N Gussev , Jeremy T Busby , Lizhen Tan
2014
Pilot Project for Irradiation Testing of Materials at the ATR―National Scientific User Facility
Kumar Sridharan , Todd R. Allen , Heather J. Maclean , Lizhen Tan
Transactions of the American Nuclear Society 100 279 -280
2009
Segregation behavior and phase instability of Eurofer97 after neutron irradiation to 72 dpa
Chad M. Parish , Kevin G. Field , Yutai Katoh , Kun Wang
Journal of Nuclear Materials 547 152834
9
2021
Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature
Xiang Chen , Lizhen Tan
Office of Scientific and Technical Information (OSTI)
2020
Microstructure and mechanical properties of high Mn-containing ferritic-martensitic alloys exposed to cyclical thermal treatment
Niyanth Sridharan , Kevin G. Field , Kurt Terrani , Lizhen Tan
Materials Science and Engineering A-structural Materials Properties Microstructure and Processing 813 141143
1
2021
Neutron irradiation induced defects and clustering in NF616 and T91
Tarik A. Saleh , Lizhen Tan , Weicheng Zhong
Journal of Nuclear Materials 552 153001
2021
Fracture toughness evaluation of select advanced replacement alloys for LWR core internals
Lizhen Tan , Xiang Chen
2017
2015
Tensile and toughness assessment of the procured advanced alloys
Lizhen Tan , Mikhail A. Sokolov , David T. Hoelzer , Jeremy T. Busby
Office of Scientific and Technical Information (OSTI)
2
2015
Final Report on Developing Microstructure-Property Correlation in Reactor Materials using in situ High-Energy X-rays
Meimei Li , Jonathan D. Almer , Yong Yang , Lizhen Tan
Office of Scientific and Technical Information (OSTI)
2016
Design and screening of nanoprecipitates-strengthened advanced ferritic alloys
Lizhen Tan , Ying Yang , Tianyi Chen , K. Sridharan
2016
Phase Stability in the Fe-Rich Fe-Cr-Ni-Zr Alloys
Tianyi Chen , Ying Yang , Lizhen Tan
Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science 48 ( 10) 5009 -5016
7
2017
Thermal Stability of Intermetallic Phases in Fe-rich Fe-Cr-Ni-Mo Alloys
Ying Yang , Lizhen Tan , Jeremy T. Busby
Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science 46 ( 9) 3900 -3908
6
2015
Experimental and Simulation Insight on the Transport of Silver Fission Product in SiC
Tyler J. Gerczak , Lizhen Tan , Todd R. Allen , Sarah Khalil
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2 715 -723
4
2008
Friction Stir Welding of ODS and RAFM Steels
Zhenzhen Yu , Zhili Feng , David Hoelzer , Lizhen Tan
Metallurgical and Materials Transactions E 2 ( 3) 164 -172
4
2015